The study of temperature dependence of interaction between dislocation and cavity in pure tungsten

Kaito Mizuno

Presentation information

Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)/601-3 Tritium Science and Technology (Fuel Recovery and Refining, Measurement, Iisotope Effect, Safe Handling)

[2G17-22] Tungsten

Wed. Mar 27, 2024 4:20 PM - 5:55 PM Room G (21Bildg.3F 21-317)

Chair:Takumi Chikada(Shizuoka Univ.)

5:20 PM - 5:35 PM

[2G21] The study of temperature dependence of interaction between dislocation and cavity in pure tungsten

*Kaito Mizuno¹, Kouichi Tougou¹, Ken-ichi Fukumoto¹, Ryoya Ishigami² (1. Univ. of Fukui, 2. WERC)

Keywords:divertor, tungsten, irradiation hardening, in-situ TEM observation, tensile test, dislocation, obstacle barrier strength

The in-situ TEM observation during tensile tests at 700 degrees Celsius was conducted employing the helium-ion-irradiated pure tungsten. And, the temperature dependences of obstacle barrier strength as hardening parameter of the Orowan model and fraction of cross-slip behavior were investigated by the interaction between cavity and dislocation.The obstacle barrier strength decreased while the fraction of cross-slip behavior increased with rising temperature.